IAEA1338 TEMPUL.

1. NAME OR DESIGNATION OF PROGRAM:  TEMPUL.

3. DESCRIPTION OF PROGRAM OR FUNCTION

A computer program for temperature distribution calculations in fuel element after the pulse.

4. METHOD OF SOLUTION

The program solves the diffusion equation for heat transfer in one-dimensional cylindrical geometry using simple finite-difference method.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The program is provided with THE necessary data-base consisting of material properties for : 1-zirconium, 2-stainless steel, 3-fuel with 12 w/o  uranium and 20% enrichment, 4-fuel with 8.5 w/o uranium and 20% enrichment, 5-FLIP fuel with 8.5 w/o uranium and 70% enrichment, 6-LEU fuel with 20 w/o uranium and 20% enrichment and 7-water. The gap can either be filled with air or with Helium. The gap also can be omitted.
The number of output-times for the radial temperature distribution is limited to 11.

6. TYPICAL RUNNING TIME:

Two hours on Intel 486/100 computer; 30 minutes on a
VAX 4000; 15 minutes CPU-time on a Pentium 166MHz; 10 minutes on DEC ALPHA computer.

7. UNUSUAL FEATURES OF THE PROGRAM

TEMPUL generates output for the DIAG program CITEDIAG. With this output a graphical representation of the output data is possible.

8. RELATED AND AUXILIARY PROGRAMS:  WIMS-D/4; DIAG.

10. REFERENCES

- Varnostno porocilo za reaktor TRIGA Mark II v Podgorici
  IJS-DP-5823,
  January 1991
- Safety Analysis Report for the 3000-kW Forced-Flow TRIGA Mark II
  Reactor for the Bangladesh Atomic Energy Commission
  Dacca, Bangladesh
  General Atomic, E-117-990, July 1981
- M.Ravnik, I.Mele, B.Zefran, PULSTRI-1 A Computer Programme
  for TRIGA Reactor Pulse Calculations,
  J.Stefan Institute Report,IJS-DP-5756, Jan. 1990
- I.Mele, M.Ravnik, TRIGAP Computer Programme, J.Stefan
  Institute Report, IJS-DP-4238, Dec. 1985
- I. Mele, M. Ravnik
  Projekt rekonstrukcije reaktorja TRIGA za pulzno obratovanje
Preracun nuklearnih lastnosti, Revizija 1, IJS-DP-5760, Marec 1990  - L. S. Tong, J. Weisman
  Thermal Analysis of Pressurized Water Reactors,
  American Nuclear Society and U.S. Atomic Energy Commission, 1971
- E.L. Wachpress
  Iterative Solution of Elyptic Systems and Applications
  to the Neutron Diffusion Equations of Reactor Physics
  Prentice-Hall, Inc., Englewood Cliffs, N.J., USA, 1966
- DIAG, 2-D Plotting Program for PDP-11/34, IAEA0891, NEA Data Bank
- WIMS-D/4, NEA Data Bank

- I. Mele, S. Slavic and M. Ravnik:
  TEMPUL - A Computer Program for Temperature Distribution
  Calculations in Fuel Element after the Pulse
  Program Manual
  IJS-DP-6523 (October 1992)

11. MACHINE REQUIREMENTS:

Output files can, depending on input options, require very much space.  Minimum disk space for all files IS 1.3 MB.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

MS-DOS, MS-WINDOWS, Open VMS, Unix

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  None.

15. NAME AND ESTABLISHMENT OF AUTHORS

    Slavko Slavic, Matjaz Ravnik
    "Jozef Stefan" Institute,
    Reactor physics division
    Jamova 39, PO. BOX 3000
    1001 Ljubljana, Slovenia
    E-mail: Slavko.Slavic@ijs.si
    E-mail: Matjaz.Ravnik@ijs.si
    and:
    Irena Mele
    Agencija za radioaktivne odpadke
    Parmova ulica 53
    1000 Ljubljana, Slovenia

File name	File description	Records
IAEA1338_01.001	information file	125
IAEA1338_01.002	sample output of test case 1	0
IAEA1338_01.003	sample input for test case 1	0
IAEA1338_01.004	sample output of test case 1	0
IAEA1338_01.005	sample output of test case 1	0
IAEA1338_01.006	sample output of test case 1	0
IAEA1338_01.007	sample output of test case 2	0
IAEA1338_01.008	sample input for test case 2	0
IAEA1338_01.009	sample output of test case 2	0
IAEA1338_01.010	sample output of test case 2	0
IAEA1338_01.011	sample output of test case 2	0
IAEA1338_01.012	list of files	0
IAEA1338_01.013	PC (MS-)DOS executable	0
IAEA1338_01.014	FORTRAN source code	0
IAEA1338_01.015	DOS file-names	15